Vol.
XXXII, No. 3, Pp. 193305
September 2017
UDC 621.039+614.876:504.06
ISSN 14513994
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Pages: 193203
Authors: Gizem Bakir and Huseyin Yapici
Abstract
This study presents the determination of fuel rejuvenation times in a DT fusion breeder reactor fuelled with a mixture of ^{nat}UO_{2} and ThO_{2} for multireuse of nuclear fuels in CANDU37 reactors. To determine the effect of thorium on the fuel enrichment and rejuvenation times, neutronic analyses are performed by increasing the percentage of ThO_{2} in the fuel mixture from 10 to 35. The timedependent neutronic calculations are carried out in three stages. In the first stage, which is the fuel enrichment or rejuvenation process in the fusion breeder reactor, the subcritical calculations of the fusion breeder reactor fuelled with the fuel mixtures are performed by using the MCNPX 2.7/CINDER under a fusion neutron wall loading of 1 MWm^{2}, corresponding to neutron flux of 4.444·10^{13} cm^{2}s^{1}^{} (energy of every fusion neutron is 14.1 MeV). In the second stage, which is the thermal reactor analysis, the fuel rods enriched at the end of the first stage are placed in the CANDU37 reactor, and the critical calculations of this reactor are performed by using MCNPX 2.7 and MONTEBURNS codes separately. The numerical results show that the neutronic values obtained from both codes are very near each other. The third stage is the twoyear cooling process of CANDU spent fuels. The values obtained by numerical calculations show that this fusion breeder reactor is selfsufficient in terms of tritium and has a high performance in terms of energy multiplication as well as fuel rejuvenation and thorium utilization.
Key words:
fusion breeder reactor, fissile breeding, fuel enrichment, fuel rejuvenation,
thorium utilization, CANDU reactor
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